PURIFICATION OF URANIUM FROM URANIUM/MOLYBDENUM ALLOY

Journal Article · Mon Oct 15 00:00:00 EDT 2007 · Separation Science and Technology

OSTI ID:919043

Pierce, R; Ann Visser, A; James Laurinat, J

The Savannah River Site will recycle a nuclear fuel comprised of 90% uranium-10% molybdenum by weight. The process flowsheet calls for dissolution of the material in nitric acid to a uranium concentration of 15-20 g/L without the formation of precipitates. The dissolution will be followed by separation of uranium from molybdenum using solvent extraction with 7.5% tributylphosphate in n-paraffin. Testing with the fuel validated dissolution and solubility data reported in the literature. Batch distribution coefficient measurements were performed for the extraction, strip and wash stages with particular focus on the distribution of molybdenum.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: DE-AC09-96SR18500
• OSTI ID: 919043
• Report Number(s): WSRC-STI-2007-00581; SSTEDS; TRN: US0806290
• Journal Information: Separation Science and Technology, Journal Name: Separation Science and Technology; ISSN 0149-6395
• Publisher: pubinfo
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALLOYS
DISSOLUTION
DISTRIBUTION
FLOWSHEETS
MOLYBDENUM
NITRIC ACID
NUCLEAR FUELS
PURIFICATION
SAVANNAH RIVER
SOLUBILITY
SOLVENT EXTRACTION
TESTING
URANIUM